Published May 2001
| Version v1
Miscellaneous
Analyses of reactor coolant flow rate decrease events using the KEPRI methodology
Description
KEPRI is developing the in-house methodology for non-LOCA safety analyses based on the codes and methodologies of vendors and EPRI. To verify the feasibility of the methodology, reactor coolant flow rate decrease events have been analyzed at the standpoint of RCS pressure. Furthermore, to assess the important parameters to RCS pressure, the sensitivity analyses have been carried out over some parameters such as reactivity feedback, reactor coolant temperature, and reactor coolant pressure. The results of these analyses have similar trends comparing with those of FSAR 15
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society spring meeting
- Imprint Pagination
- [ONE CDROM]
- Journal Page Range
- [14 p.]
Conference
- Title
- 2001 spring meeting of the Korean Nuclear Society
- Dates
- 24-25 May 2001
- Place
- Cheju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33040457
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLANTS; EPRI; FEASIBILITY STUDIES; FEEDBACK; FLOW RATE; KOREAN ORGANIZATIONS; R CODES; SAFETY ANALYSIS; SENSITIVITY ANALYSIS
- Descriptors DEC
- COMPUTER CODES; NATIONAL ORGANIZATIONS
Optional Information
- Notes
- 9 refs, 16 figs, 6 tabs